ML031290100

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Summary of Annual Assessment Meeting with Entergy Nuclear Operations, Inc
ML031290100
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 05/08/2003
From: Brian Holian
Division Reactor Projects I
To:
Shared Package
ML030620067 List:
References
FOIA/PA-2003-0379, FOIA/PA-2003-0388, SIP Test Sample upto2-6-04
Download: ML031290100 (3)


Text

May 8, 2003 MEETING

SUMMARY

LICENSEE: ENTERGY NUCLEAR OPERATIONS, INC.

FACILITY: INDIAN POINT NUCLEAR GENERATING STATION, Units 2 & 3

SUBJECT:

SUMMARY

OF APRIL 28, 2003, ANNUAL ASSESSMENT MEETING WITH ENTERGY NUCLEAR OPERATIONS, INC.

On April 28, 2003 at 6:00 p.m., an annual assessment meeting was conducted at Crystal Bay on the Hudson, Peekskill, New York, between the Nuclear Regulatory Commission (NRC) and Entergy Nuclear Operations. The NRC presented and discussed its assessment of the safety performance of Indian Point Units 2 and 3 for the period between January 1 through December 31, 2002.

The NRC presentation included background on both plants, performance assessment results for calendar year 2002, an overview of 2003 planned inspections and oversight, and a discussion of general NRC issues, which included the topics of security and emergency planning. As part of this regulatory performance meeting, Entergy presented an overview of the areas of Operations, Maintenance, and Engineering. Numerous Entergy performance indicators were presented. NRC staff from the region and HQ, who had performed a site visit that day, questioned Entergy on their performance results, particularly in the areas of human performance, corrective actions, and engineering projects.

At the end of the meeting between the NRC and Entergy Nuclear Operations, public attendees were offered the opportunity to ask questions of NRC officials. This question and answer period lasted approximately two and a half hours. Topics discussed included various aspects of plant performance, which included questions about backlogs of work and corrective action items. Numerous comments and questions related to emergency preparedness. Many individuals stated that an emergency evacuation would simply not work in such a congested area. One individual questioned the NRC response to an inquiry on spent fuel pool safety. The Unit 2 and 3 spent fuel pools are constructed of reinforced concrete. The pools are situated in low-rise spent fuel buildings situated among the much taller Unit 2 and 3 containment buildings.

The spent fuel rods are stored at the bottom of the pools and are covered by over 20 feet of water. Unit 2 spent fuel is entirely below grade and the Unit 3 spent fuel is partially above grade (due to the slant of grade level on the Unit 3 side of the site). The NRC staff had follow-up discussions to clarify this aspect of the Unit 3 fuel pool design with the individual. This clarification is provided to ensure other meeting attendees are afforded the same corrected plant design information.

2 Questions raised by local media were also addressed by the NRC. Feedback forms submitted by the public immediately following the meeting will be evaluated. The presentation slides and the attendance list can be located in the Agencywide Documents Access and Management Systems (ADAMS) by referring to Accession No. ML030620067 and ML030620074. ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html.

Sincerely,

/RA/

Brian Holian, Deputy Director Division of Reactor Projects DOCUMENT NAME: G:\BRANCH2\Meetings\MeetingSummary28April2003Rev2.wpd After declaring this document An Official Agency Record it will/will not be released to the Public. To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy OFFICE RI/DRP RI/DRP NAME WCook/WAC BHolian/BEH DATE 05/8/03 05/8/03 OFFICIAL RECORD COPY